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List of results

• ML19351C996  + (Forwards WCAP-9469, Analysis of Capsule U from Portland General Electric Co Trojan Reactor Vessel Radiation Surveillance Program. Capsule U Removed from Reactor Vessel for Surveillance in Apr 1978)
• ML20050B312  + (Forwards WCAP-9500 & WCAP-9401/9402 NRC Safety Evaluation Re Mixed Core Compatibility Items.Proprietary Response Withheld (Ref 10CFR2.790))
• ML19242A349  + (Forwards WCAP-9500, Ref Core Rept:17 X 17 Optimized Fuel Assembly)
• ML19330C661  + (Forwards WCAP-9500,Amend 1, Ref Core Rept 17x17 Optimized Fuel Assembly)
• ML13333A491  + (Forwards WCAP-9544, Metallurgical Investigations of Cracks in Steam Generator Feedwater Lines. Rept Suggests Cracking Occurred Early in Plant Life & Has Not Progressed.W/O Encl)
• ML17249A286  + (Forwards WCAP-9563, Metallurgical Investigation of Steam Generator Feedwater Piping Cracks at Robert Emma Ginna Nuclear Power Generating Station, in Response to IE Bulletin 79-13.W/o Encl)
• ML19208C446  + (Forwards WCAP-9585, Analysis of Delayed Reactor Coolant Pump Trip During Small LOCA for Westinghouse NSSS, Nonproprietary Version)
• ML19209A562  + (Forwards WCAP-9587, Study of Two-Phase Natural Circulation Following Small LOCA Using Notrump Code, Nonproprietary Version of WCAP-9586)
• ML19340C512  + (Forwards WCAP-9613, Integrity Assessment of Feedwater Line Indications,Trojan Nuclear Plant, to Suppl Response to IE Bulletin 79-13 Re Cracking.Rept Concludes That Indication Adjacent to nozzle-to-reducer Weld Is Acceptable)
• ML19256F627  + (Forwards WCAP-9639, Rept on Small Break Accidents for Westinghouse NSSS W/Upper Head Injection, Nonproprietary Version)
• ML17250A308  + (Forwards WCAP-9663, Metallurgical Investigation of Cracks in Pressurizer Nozzle-to-Safe-End Weld of Robert Emmett Ginna Nuclear Power Generating Station. Rept Is Followup to LER 79-023)
• ML19322E902  + (Forwards WCAP-9691, Transient & Accident Analysis, in Compliance W/Item 2.1.9.c of NUREG-0578)
• ML19320A764  + (Forwards WCAP-9748 & WCAP-9749, Westinghouse Owners Group Asymmetric LOCA Load Evaluation,Phase C. Proprietary Version Withheld (Ref 10CFR2.790).Application for Witholding Proprietary Info Encl)
• ML19321A117  + (Forwards WCAP-9753 & WCAP-9754 Re Inadequate Core Cooling Studies & Vendor 800711 Application for Withholding Info W/ Supporting Affidavit.Repts Will Provide Analytical Basis for Guidelines Re Inadequate Core Cooling Detection & Remedy)
• ML19332A999  + (Forwards WCAP-9764 & WCAP-9765,proprietary & Nonproprietary Version of, Documentation of Westinghouse Core Uncovery Tests & Small Break Evaluation Model Core Mixture Level Model. Proprietary Version Withheld (Ref 10CFR2.790))
• ML19350A469  + (Forwards WCAP-9804, Probabilistic Analysis & Operational Data in Response to Item II.K.3.2 for Westinghouse NSSS Plants)
• ML20010C834  + (Forwards WCAP-9842, Union Electric Co,Callaway Unit 1, Reactor Vessel Radiation Surveillance Program)
• ML20010C835  + (Forwards WCAP-9842, Union Electric Co,Callaway Unit 1, Reactor Vessel Radiation Surveillance Program.)
• ML20031F225  + (Forwards WCAP-9946, Reliability Analysis of Auxiliary Feedwater Sys for Catawba Nuclear Station Units 1 & 2, Per NUREG-0737,Item II.E.1.1)
• ML20138E816  + (Forwards WCGS Annual Radioactive Effluent Release Rept for 960101-961231 & Rev 0 to AP 07B-003, Odcm.)
• ML20138E811  + (Forwards WCGS Annual Radioactive Effluent Release Rept for 960101-961231 & Rev 0 to AP 07B-003, Odcm)
• ML20091G326  + (Forwards WCGS Emergency Preparedness Field Exercise Scenario for 1995 Exercise Scheduled to Be Conducted 950815 & 16)
• ML20070D694  + (Forwards WCGS NPDES Renewal Application,Including Subsequent Ltrs & 0524 to Ks Dept of Health & Environ W/Addl Permit Renewal Info)
• ML20141K644  + (Forwards WCNOC Supplier Quality Rept of NUPIC Joint Audit Performed by Wcnoc,Union Electric & TVA of Brea,California Facility on 970122-23 & Little Rock,Ar Facility on 970128-31)
• ML20040F440  + (Forwards WE Bergholz & L Silverstrom Notices of Appearance. Gh Cunningham,Rk Olson & Ja Wilderotter Appearances Withdrawn.Certificate of Svc Encl)

• ML20055G744  + (Forwards WE Dressler for Action)

• ML20070R465  + (Forwards WE Knapp 820720 & E Stanley s Re DOE Request for Early Site Preparation for Consideration in Rept)
• ML19294B922  + (Forwards WE Scott Documents Per ASLB 800214 Order & DOJ 800221 Motion for Protective Order Re Certain of Tx Util Co Sys Documents)
• ML19294B923  + (Forwards WE Scott Documents Per ASLB 800214 Order & DOJ 800221 Motion for Protective Order Re Certain of Tx Util Co Sys Documents)
• ML19289G017  + (Forwards WE Wallace Ltr Re Chemical Explosive Hazard at Tmi. Info Partially Withheld:Address and Telephone Numbers (Ref FOIA Exemption 6))
• ML20136B746  + (Forwards WE Wallace Re Formation of Zirconium Hydride in Reactor Core as Core Cools.Hydrogen Produced by Accident Still Present & Represents Grave Explosion Hazard)
• ML20128P407  + (Forwards WG/2-81/7 & Sindoc (82) 50,in Response to Request. W/O Encls)
• ML20128P321  + (Forwards WG/2-81/7 NEA & SINDOC(82) 50 Re Source Terms,In Response to Request.W/O Encls)
• ML20154Q445  + (Forwards WM-3951-5, Development of Regulatory Guidance for Determining Waste Classification Vols & Masses, Technical Ltr Rept)
• ML20153C334  + (Forwards WM-3951-6, Evaluation of Gypsum Cement Softening, Technical Ltr Rept)
• ML20153D846  + (Forwards WM-3951-6, Evaluation of Gypsum Cement Softening, Technical Ltr Rept)
• ML20154F723  + (Forwards WM-3951-6, Evaluation of Gypsum Cement Softening, Per 880915 Telcon & 880913 MG Cowgill Memo Re Addl Info on Gypsum Softening Containing Info Received After Finalized Technical Rept.Encl Rept Withheld)
• ML20211G612  + (Forwards WMC-057, Mgt Plan for Extended Const Delay of WNP-1,Executive Summary (Levels I-III) & Rev 4 to WMC-050A, Mgt Plan for Extended Const Delay of WNP-3,Executive Summary (Levels I-III))
• GO2-88-140, Forwards WNP-2 Annual Emergency Exercise - 1988 Objectives & Limitations as First 75-day Submittal to Annual Exercise Program.Remaining 45-day Submittal Will Remain Detailed Description of Exercise Scenario & Actions  + (Forwards WNP-2 Annual Emergency Exercise - 1988 Objectives & Limitations as First 75-day Submittal to Annual Exercise Program.Remaining 45-day Submittal Will Remain Detailed Description of Exercise Scenario & Actions)
• GO2-85-054, Forwards WNP-2 Annual Emergency Exercise - 1986, Providing Objectives & Limitations as 75-day Submittal to Annual Exercise Program.Remaining 45-day Submittal Will Contain Detailed Description of Exercise Scenario  + (Forwards WNP-2 Annual Emergency Exercise - 1986, Providing Objectives & Limitations as 75-day Submittal to Annual Exercise Program.Remaining 45-day Submittal Will Contain Detailed Description of Exercise Scenario)
• GO2-87-020, Forwards WNP-2 Annual Emergency Exercise 1987 Objectives & Limitations as First Submittal to Annual Exercise Program. Remaining Submittal Will Contain Detailed Description of Exercise Scenario & Anticipated Actions  + (Forwards WNP-2 Annual Emergency Exercise 1987 Objectives & Limitations as First Submittal to Annual Exercise Program. Remaining Submittal Will Contain Detailed Description of Exercise Scenario & Anticipated Actions)
• ML17291A685  + (Forwards WNP-2 Cycle 10 COLR, COLR 94-10,Rev 2.Rev Incorporates Extended Single Loop Max Average Planar Linear Heat Generation Rate Limits for SPC 9x9 Reload & Lead Fuel Assembly Fuel)
• GO2-95-047, Forwards WNP-2 Cycle 10 COLR, COLR 94-10,Rev 2.Rev Incorporates Extended Single Loop Max Average Planar Linear Heat Generation Rate Limits for SPC 9x9 Reload & Lead Fuel Assembly Fuel  + (Forwards WNP-2 Cycle 10 COLR, COLR 94-10,Rev 2.Rev Incorporates Extended Single Loop Max Average Planar Linear Heat Generation Rate Limits for SPC 9x9 Reload & Lead Fuel Assembly Fuel)
• GO2-98-203, Forwards WNP-2 Feedwater Nozzle Insp Rept for R-13 Maint & Refueling Outage.Rept Submitted Pursuant to Commitments Made in Response to NUREG-0619, BWR Feedwater Nozzle & Control Rod Drive Return Line Nozzle Cracking  + (Forwards WNP-2 Feedwater Nozzle Insp Rept for R-13 Maint & Refueling Outage.Rept Submitted Pursuant to Commitments Made in Response to NUREG-0619, BWR Feedwater Nozzle & Control Rod Drive Return Line Nozzle Cracking)
• GO2-99-021, Forwards WNP-2 Fitness for Duty Semiannual Performance Data Rept for Jul-Dec 1998,per 10CFR26.71(d).Data Has Been Analyzed & Mgt Actions Have Been Taken to Enhance FFD Program  + (Forwards WNP-2 Fitness for Duty Semiannual Performance Data Rept for Jul-Dec 1998,per 10CFR26.71(d).Data Has Been Analyzed & Mgt Actions Have Been Taken to Enhance FFD Program)
• GO2-97-182, Forwards WNP-2 ISI Summary Rept for Refueling Outage RF12  + (Forwards WNP-2 ISI Summary Rept for Refueling Outage RF12)
• ML17292B077  + (Forwards WNP-2 ISI Summary Rept for Refueling Outage RF12.)
• ML17291B016  + (Forwards WNP-2 ISI Summary Rept for Tenth Refueling Outage, Including NIS-1 Owner Data Rept for ISI & NIS-2 Owner Repts for Repairs & Replacements)
• GO2-95-175, Forwards WNP-2 ISI Summary Rept for Tenth Refueling Outage, Including NIS-1 Owner Data Rept for ISI & NIS-2 Owner Repts for Repairs & Replacements  + (Forwards WNP-2 ISI Summary Rept for Tenth Refueling Outage, Including NIS-1 Owner Data Rept for ISI & NIS-2 Owner Repts for Repairs & Replacements)
• ML17284A748  + (Forwards WNP-2 Inservice Insp Summary Rept for Refueling Outage RF13 Spring,1998, Per Section XI of ASME Boiler & Pressure Vessel Code Article IWA-6240)
• GO2-98-163, Forwards WNP-2 Inservice Insp Summary Rept for Refueling Outage RF13 Spring,1998, Per Section XI of ASME Boiler & Pressure Vessel Code Article IWA-6240  + (Forwards WNP-2 Inservice Insp Summary Rept for Refueling Outage RF13 Spring,1998, Per Section XI of ASME Boiler & Pressure Vessel Code Article IWA-6240)